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Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Nagaya, Yasunobu; Tada, Kenichi; et al.
EPJ Web of Conferences, 284, p.14001_1 - 14001_7, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)Tada, Kenichi; Nagaya, Yasunobu; Taninaka, Hiroshi; Yokoyama, Kenji; Okita, Shoichiro; Oizumi, Akito; Fukushima, Masahiro; Nakayama, Shinsuke
Journal of Nuclear Science and Technology, 21 Pages, 2023/04
Times Cited Count：6 Percentile：98.92(Nuclear Science & Technology)The new version of the Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. This paper demonstrates the validation of JENDL-5 for fission reactor applications. Benchmark calculations are performed with the continuous-energy Monte Carlo codes MVP and MCNP and the deterministic code system MARBLE. The benchmark calculation results indicate that the performance of JENDL-5 for fission reactor applications is better than that of the former library JENDL-4.0.
Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Abe, Yutaka*; Tsubakihara, Kosuke*; Okumura, Shin*; Ishizuka, Chikako*; Yoshida, Tadashi*; et al.
Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01
Times Cited Count：64 Percentile：99.99(Nuclear Science & Technology)Kamiya, Tomohiro; Ono, Ayako; Tada, Kenichi; Akie, Hiroshi; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
Proceedings of 29th International Conference on Nuclear Engineering (ICONE 29) (Internet), 8 Pages, 2022/11
JAEA started to develop the advanced reactor analysis code JAMPAN (JAEA advanced multi-physics analysis platform for nuclear systems). The current version of JAMPAN handles the continuous energy Monte Carlo code MVP and the detailed thermal-hydraulics analysis code for multiphase and multicomponent JUPITER. JAMPAN is designed to consider the extensibility and it does not depend on the analysis codes. All calculations in JAMAPAN are not directly connected. JAMPAN has data containers, and all input and output data of each analysis code are set in these data containers. JAMPAN will easily exchange the calculation codes and add the other calculations, e.g., structure calculation and irradiation calculation since the input and the output format of each code has no impact on the other calculation codes. The 4 by 4 pin-cell geometry was used as the demonstration calculation of JAMPAN and the physically reasonable calculation results were obtained.
Kono, Takahiko; Shimo, Michikuni*; Hayakawa, Hironobu*; Taniguchi, Kazufumi*; Tanaka, Masato*; Tanaka, Hitomi*; Onoue, Yosuke*; Nagaya, Hiroshi*; Torii, Hiroyuki*; Uno, Kazuko*
Hoken Butsuri (Internet), 55(4), p.226 - 238, 2020/12
After the accident at the Fukushima Daiichi Nuclear Power Station, artificial radionuclides such as radioactive cesium and iodine were released into the environment. It caused great anxiety not only in the vicinity of the Fukushima Daiichi Nuclear Power Station but also in other regions of Japan. Some members of the Japan Health Physics Society (JHPS) which is a leading academic society in Japan in the field of radiation protection volunteered to establish the website called "Question and Answer about radiation in Daily Life" just after the accident to reduce the anxiety of the residents about the health effects of radiation. After that, Committee of "Question and Answer about radiation in Daily Life" was established in August 2011 in JHPS, and this activity had been carried out under the responsibility of the society that answered with sincerity against questions from the public as specialists until February 2013. The number of questions on the website had gradually decreased as time passed; therefore, the Committee members decided to end these activities in February 2013. In this paper, following contents were shown; the activities of the Q&A website for about two years, the issues of the stance on our activities, the information related to the website activities and the analysis of Twitter data. Based on the experience and the knowledge obtained from these activities, the issues and experiences that can be utilized in the initial response to emergencies for radiation protection experts as well as other fields are presented.
Ishiyama, Atsushi*; Ueda, Hiroshi*; Fukuda, Mitsuhiro*; Hatanaka, Kichiji*; Miyahara, Nobuyuki*; Yokota, Wataru; Kashima, Naoji*; Nagaya, Shigeo*
Denki Gakkai Kenkyukai Shiryo, Chodendo Oyo Denryoku Kiki Kenkyukai (ASC-10-33), p.83 - 88, 2010/06
Therapy of tumor using radiation, especially heavy particle, is one of the effective treatment for an aged person and a malignant solid tumor. In order to spread the radiation therapy, downsizing of accelerator is necessary for reduction of its vast costs of construction and running. The quality of high temperature superconductors is improving rapidly in recent years, which may lead to realization of the downsizing. This presentation describes a conceptual design of the superconducting cyclotron and its advantage comparing to other type of accelerators.
Ueda, Kiyoshi*; Fukuzawa, Hironobu*; Liu, X.*; Sakai, Katsunori*; Pr
mper, G.*; Morishita, Yuichiro*; Saito, Norio*; Suzuki, Isao*; Nagaya, Kiyonobu*; Iwayama, Hiroshi*; et al.
Journal of Electron Spectroscopy and Related Phenomena, 166-167, p.3 - 10, 2008/11
Times Cited Count：23 Percentile：72.33(Spectroscopy)Interatomic Coulombic decay (ICD) in Ar
, ArKr and Kr following Ar 2p or Kr 3d Auger decay has been investigated by means of momentum-resolved electron-ion-ion-coincidence spectroscopy. This sequential decay leads to Coulombic dissociation into dication and monocation. Simultaneously determining the kinetic energy of the ICD electron and the kinetic energy release between the two atomic ions, we could unambiguously identify the ICD channels. We find that, in general, spin conserved ICD, in which the singlet (triplet) dicationic state produced via the atomic Auger decay preferentially decays to the singlet (triplet) state, transferring the energy to the other atom, is faster than the spin-flip ICD, in which the Auger final singlet (triplet) dicationic state decays to the triplet (singlet) state.
Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.
JAERI-Research 2004-008, 383 Pages, 2004/06
JAERI-Research-2004-008.pdf:21.49MB
The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.
Sugie, Tatsuo; Hatae, Takaki; Koide, Yoshihiko; Fujita, Takaaki; Kusama, Yoshinori; Nishitani, Takeo; Isayama, Akihiko; Sato, Masayasu; Shinohara, Koji; Asakura, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.482 - 511, 2002/09
Times Cited Count：6 Percentile：3.03(Nuclear Science & Technology)The diagnostic system of JT-60U (JT-60upgrade) is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters have been improved, so that the internal structure of plasmas has been explored. The understanding of plasma confinement has been enhanced by density and temperature fluctuation measurements using a mm-wave reflectometer and electron cyclotron emission measurements respectively. In addition, the real-time control experiments of electron density, neutron yield, radiated power and electron temperature gradient have been carried out successfully by corresponding diagnostic devices. These measurements and the real time control contribute to improving plasma performance. Diagnostic devices for next generation fusion devices such as a CO2 laser interferometer/polarimeter and a CO2 laser collective Thomson scattering system have been developed.
Kawanishi, Tomohiro; Nagaya, Yasunobu; Yoshida, Hiroyuki; Akie, Hiroshi; Tada, Kenichi; Ono, Ayako
no journal, ,
JAEA has started to develop the advanced neutronics/thermal-hydraulics coupling simulation system for improvement of the light water reactor analysis and safety. This simulation system uses a continuous energy Monte Carlo calculation code MVP and CFD calculation code TPFIT and JUPITER. The advanced system can treat rigorous bubble shape and it does not adopt the approximate expression and empirical formula. The advanced system will be a reference system for the current neutronics/thermal-hydraulics coupling simulation system. In this presentation, we show the outline of the advanced system.
Tada, Kenichi; Akie, Hiroshi; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
JAEA has started to develop the advanced neutronics/thermal-hydraulics coupling simulation system for improvement of the light water reactor analysis and safety. We developed a prototype simulation system to find the issues of coupling simulation and to investigate the optimum mesh size for neutronics and thermal-hydraulics analysis. This presentation explains the overview of the prototype simulation system and its calculations results.
Akie, Hiroshi; Tada, Kenichi; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
Japan Atomic Energy Agency is developing an advanced neutronics/thermal-hydraulics coupling simulation system for the design advancement and the safety improvement of light water reactors. In this presentation, an impact of the fine-scale void distribution in sub-channels on neutronics calculations is studied.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
JAEA is developing the advanced neutronics/thermal-hydraulics coupling simulation system to improve the design and safety analysis of light water reactors. This presentation explains the coupling simulation system using a continuous energy Monte Carlo code MVP and a subchannel analysis code NASCA.
Kamiya, Tomohiro; Ono, Ayako; Tada, Kenichi; Akie, Hiroshi; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA is developing a platform JAMPAN for multiphysics simulation to realize advanced neutronics/thermal-hydraulics coupling simulation for improving design and safety of light water reactors. Flexibility and modularity are required for the platform; users can perform various multiphysics simulation by choosing combination of codes simulating various phenomena such as neutron transport, heat transfer/multi-phase flow, chemical reactions etc., and can easily replace and add independent codes. To meet these requirements, JAMPAN has a common data container and every data exchange between independent codes is conducted through the data container. In this presentation, we will explain an overview of JAMPAN and show results of neutronics/thermal-hydraulics simulation on 4
4 bundle system using MVP and JUPITER as an example of JAMPAN simulation.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
We implemented the handling module for the subchannel analysis code NASCA on the multi-physics platform JAMPAN. This function is used for the neutronics/thermal-hydraulics coupling simulation. The MVP/NASCA coupling calculation on JAMPAN will be applied to the large-scale calculation e.g., a whole core analysis. The calculation results of JAMPAN were compared to those of the prototype simulation system IPACS. The calculation results of JAMPAN showed good agreement with those of IPACS.
